Neutron irradiation damage modelling of interface strengthened ferritic superalloys for high temperature fusion applications

用于高温聚变应用的界面强化铁素体高温合金的中子辐照损伤建模

• 批准号: 2462023
• 金额: --
• 依托单位: Imperial College London
• 依托单位国家: 英国
• 项目类别: Studentship
• 财政年份: 2020
• 资助国家: 英国
• 起止时间: 2020 至 无数据
• 项目状态: 未结题
• 来源: https://gtr.ukri.org/projects?ref=studentship-2462023
• 关键词: Neutron; irradiation; damage; modelling; interface

This project supported by UKAEA at the Culham Centre for Fusion Energy will explore irradiation damage in a new class of steels strengthened by additions of Ni and Al to create precipitates where the interfacial properties with the Fe-matrix can be tuned. The precipitates allow these superalloy steels to operate at much higher temperatures than current steels, with behaviours similar to Ni-based superalloys used in the gas turbines. This will be crucial for fusion reactors, such as DEMO where current steels will neither be able to survive the high temperatures or the intense neutron damage. We hypothesise that at the atomic scale the precipitate-matrix interfaces can also be useful for imparting radiation tolerance by acting as sinks for defects such as the vacancies created by the irradiation damage. The project will use, test and develop existing atomic potentials for the Fe-NiAl systems and irradiation will be simulated using molecular dynamics cascades. This work will be alongside experimental projects being run at the University of Birmingham and the student is also expected to have strong interactions with their industrial supervisors at Culham Centre for Fusion Energy.

该项目由卡勒姆聚变能中心的UKAEA支持，将探索通过添加Ni和Al来增强新型钢的辐照损伤，以产生沉淀物，其中可以调节与Fe基体的界面特性。沉淀物使这些超级合金钢能够在比当前钢高得多的温度下工作，其行为类似于燃气轮机中使用的镍基超级合金。这对聚变反应堆至关重要，例如DEMO，目前的钢既不能承受高温，也不能承受强烈的中子损伤。我们假设，在原子尺度上的沉淀-基质界面也可以是有用的，通过作为缺陷，如由辐射损伤产生的空位的汇赋予辐射耐受性。该项目将使用、测试和开发Fe-NiAl系统的现有原子势，并将使用分子动力学级联模拟辐照。这项工作将与伯明翰大学正在进行的实验项目一起进行，预计学生还将与卡勒姆聚变能源中心的工业主管进行强有力的互动。